Seismic Strength Evaluation of Corroded Reactor Containment Building
Abstract The purpose of this study is to investigate the effects of the corrosion phenomenon on the seismic strength of a reactor containment building (RCB) in nuclear power plants (NPPs). A corrosion degradation model is proposed based on the rationale of NPP structures and applied to the reinforce...
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SpringerOpen
2025-01-01
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Series: | International Journal of Concrete Structures and Materials |
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Online Access: | https://doi.org/10.1186/s40069-024-00734-4 |
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author | Md Samdani Azad Duy-Duan Nguyen Bidhek Thusa Tae-Hyung Lee |
author_facet | Md Samdani Azad Duy-Duan Nguyen Bidhek Thusa Tae-Hyung Lee |
author_sort | Md Samdani Azad |
collection | DOAJ |
description | Abstract The purpose of this study is to investigate the effects of the corrosion phenomenon on the seismic strength of a reactor containment building (RCB) in nuclear power plants (NPPs). A corrosion degradation model is proposed based on the rationale of NPP structures and applied to the reinforcements near the base mat of RCB. Three corrosion levels associated with the service life of the structure up to 60 years are considered in this study. Seven different cases are considered depending on the location of corrosion. A series of pushover analyses are performed to evaluate the seismic responses of the corroded RCB, considering all cases with different levels of damage due to corrosion. The results are obtained in terms of global responses, in which capacity curves, base shear at different limit states, demand–capacity ratios, and reserve strength ratios (RSR) are quantified. The findings of this study demonstrate that corrosion can cause a reduction in structural capacity in terms of base shear of up to 19.5% during its service life of 60 years and that is dependent on how the corrosion is propagated within RCB. The results also illustrate that corrosion in the elements in the tension zone increases the sensitivity of the responses subjected to seismic loads. |
format | Article |
id | doaj-art-e7f69c60f17546d59ebfef51d9ff2805 |
institution | Kabale University |
issn | 2234-1315 |
language | English |
publishDate | 2025-01-01 |
publisher | SpringerOpen |
record_format | Article |
series | International Journal of Concrete Structures and Materials |
spelling | doaj-art-e7f69c60f17546d59ebfef51d9ff28052025-01-19T12:14:34ZengSpringerOpenInternational Journal of Concrete Structures and Materials2234-13152025-01-0119111410.1186/s40069-024-00734-4Seismic Strength Evaluation of Corroded Reactor Containment BuildingMd Samdani Azad0Duy-Duan Nguyen1Bidhek Thusa2Tae-Hyung Lee3Department of Civil and Environmental Engineering, Yonsei UniversityDepartment of Civil Engineering, Vinh UniversityDepartment of Civil and Environmental Engineering, Hanbat National UniversityDepartment of Civil and Environmental Engineering, Konkuk UniversityAbstract The purpose of this study is to investigate the effects of the corrosion phenomenon on the seismic strength of a reactor containment building (RCB) in nuclear power plants (NPPs). A corrosion degradation model is proposed based on the rationale of NPP structures and applied to the reinforcements near the base mat of RCB. Three corrosion levels associated with the service life of the structure up to 60 years are considered in this study. Seven different cases are considered depending on the location of corrosion. A series of pushover analyses are performed to evaluate the seismic responses of the corroded RCB, considering all cases with different levels of damage due to corrosion. The results are obtained in terms of global responses, in which capacity curves, base shear at different limit states, demand–capacity ratios, and reserve strength ratios (RSR) are quantified. The findings of this study demonstrate that corrosion can cause a reduction in structural capacity in terms of base shear of up to 19.5% during its service life of 60 years and that is dependent on how the corrosion is propagated within RCB. The results also illustrate that corrosion in the elements in the tension zone increases the sensitivity of the responses subjected to seismic loads.https://doi.org/10.1186/s40069-024-00734-4Reactor containment buildingBeam–truss modelCorrosionPushover analysisDemand–capacity ratioReserve strength ratio |
spellingShingle | Md Samdani Azad Duy-Duan Nguyen Bidhek Thusa Tae-Hyung Lee Seismic Strength Evaluation of Corroded Reactor Containment Building International Journal of Concrete Structures and Materials Reactor containment building Beam–truss model Corrosion Pushover analysis Demand–capacity ratio Reserve strength ratio |
title | Seismic Strength Evaluation of Corroded Reactor Containment Building |
title_full | Seismic Strength Evaluation of Corroded Reactor Containment Building |
title_fullStr | Seismic Strength Evaluation of Corroded Reactor Containment Building |
title_full_unstemmed | Seismic Strength Evaluation of Corroded Reactor Containment Building |
title_short | Seismic Strength Evaluation of Corroded Reactor Containment Building |
title_sort | seismic strength evaluation of corroded reactor containment building |
topic | Reactor containment building Beam–truss model Corrosion Pushover analysis Demand–capacity ratio Reserve strength ratio |
url | https://doi.org/10.1186/s40069-024-00734-4 |
work_keys_str_mv | AT mdsamdaniazad seismicstrengthevaluationofcorrodedreactorcontainmentbuilding AT duyduannguyen seismicstrengthevaluationofcorrodedreactorcontainmentbuilding AT bidhekthusa seismicstrengthevaluationofcorrodedreactorcontainmentbuilding AT taehyunglee seismicstrengthevaluationofcorrodedreactorcontainmentbuilding |